原子能科学技术2012，Vol.46Issue(z1)：295-300,6.
AP1000给水丧失事故定性分析
Qualitative Accident Analysis on Loss of Normal Feedwater for AP1000
李延凯 1林萌 1侯东 1李美琳 1杨燕华1
作者信息
- 1. 上海交通大学核科学与工程学院,上海200240
- 折叠
摘要
Abstract
For the analysis of loss of normal feedwater accident for AP1000, a thermal-hydraulic model was built based on a two-fluid best estimate code, RELAP5. A control system model was built based on Matlab/Simulink code. As the main data for modeling was from AP1000 Design Control Document (AP1000 DCD), which was inadequate and not accurate enough, the accident analysis was qualitative. The calculation results, overall consistent with the same accident in DCD, show that the RELAP5 code has the ability to calculate the natural circulation. PRHRS and CMT are able to remove the core residual heat, decay heat timely and efficiently during the accident to guarantee the safety of the core. In the calculation model, the capability of PRHRS is stronger, which makes the coolant temperature quickly reduced to a lower level, leading to an earlier actuation of CMT, followed by different responses of the plant.关键词
AP1000/给水丧失/PRHRS/CMTKey words
AP1000/ loss of normal feedwater/ PRHRS/ CMT分类
能源科技引用本文复制引用
李延凯,林萌,侯东,李美琳,杨燕华..AP1000给水丧失事故定性分析[J].原子能科学技术,2012,46(z1):295-300,6.
